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Title: PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING SEPTEMBER, 1960

Abstract

The study of possible reactions induced by the application of high pressures at high temperatures was concentrated on U/sub 3/O/sub 8/-Al/sub 2/O/ sub 3/. Data are reported on the effects of temperature on the tensile properties of fully recryatallized Cr-- Hb, Nb-- V, Nb-- Zr, and Cr-- Nb-- Zr alloys. The effect of radiation on the creep properties of Zircaloy-2 at elevated temperatures is being studied. Magnesium oxides are being evaluated as a fuel matrix material for uranium dioxide. Specimens of niobium-base birary alloys containing 10, 20, and 30 wt.% uranium and ternary alloys containing 20 wt.% uranium with 10 or 20 wt.% Zr were prepared with enriched uranium for irradiation tests. Pu--Nb, Pu-- Th, Mo-- Pu-- U, and Nb-- Pu--U alloys were selected as candidates in the search for improved irradiation resistance. Specimens consisting of uranium nitride dispersed in C, Cr, Fe, Mo, Nb, Ta, Ti, W, and Zr were fabricated and heat-treated to evaluate compatibility. A summary of results is presented from 3 hr, 1430 deg C, 5 tsi hydrostatic pressings of various types of uranium carbide and U--C -Nb systems. The effects of heat- treatment on some properties of U-C syatems are presented. Data are presented onmore » the corrosion resistance of UC -Mo/sub 2/C, UC --NbC, UC -TiC, UC --VC, Uc -- ZrC --Mo/sub 2/C, and UC -- ZrC --VC to Santowax R at 350 C for7 days. The development of powder metallurgy and melting and casting techniques for uranium nitrides is reported. Creep and atress-rupture tests are reported on Zircaloy-2 sheet specimens. Fission gas release experiments are reported on fueled-graphite spheres in suppent of the Pebble-bed Reactor. In the development of container materials for LAMPRE applications, the fabrication behavior of 13 birary tantalum- base alloys was investigated. Radiation-effects studies of fuel specimens of UO/ sub 2/ dispersed in BeO and Al/sub 2/O/sub 3/ and UC and UC/sub 2/ dispersed in graphite are reported. Studies are being conducted to develop an instrumented fuel plate for irradiation in the SM-1 and to develop fuel, absorber, and suppressor materials for the SM-2. A process is being investigated for the fabrication of dense BeO--UC/sub 2/ fuel pellets by cold pressing and sintering. A program to study the effects of irradiation on Hastelloy-X-clad compacts of highly enriched UC/sub 2/ is in progress. Thorium samples were nickel plated for corrosion testing under atmospheric conditions and in watersaturated air at 120 and 200 deg F. Data are reported on the corrosion of thorium, uranium, and U--10 wt.% Mo alloy under three types of conditions. (For preceding period see BMI- 1464.) (W.L.H.)« less

Authors:
;
Publication Date:
Research Org.:
Battelle Memorial Inst., Columbus, Ohio
OSTI Identifier:
4086627
Report Number(s):
BMI-1469
NSA Number:
NSA-15-011448
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-61
Country of Publication:
Country unknown/Code not available
Language:
English
Subject:
METALS, CERAMICS, AND OTHER MATERIALS; ABSORPTION; AIR; ALUMINUM OXIDES; BERYLLIUM OXIDES; CARBON; CASTING; CHROMIUM; CHROMIUM ALLOYS; CORROSION; CREEP; DISPERSIONS; ELECTRODEPOSITION; ENRICHMENT; FISSION PRODUCTS; FUEL CANS; GASES; GRAPHITE; HEAT TREATMENTS; HIGH TEMPERATURE; IRON; IRRADIATION; MAGNESIUM OXIDES; MATERIALS TESTING; MELTING; METALLURGY; MOLYBDENUM; MOLYBDENUM ALLOYS; MOLYBDENUM CARBIDES; NICKEL; NIOBIUM; NIOBIUM ALLOYS; NIOBIUM CARBIDES; NITRIDES; PEBBLE BED; PLUTONIUM ALLOYS; POWDERS; PRESSURE; SINTERING; SPHERES; STRESSES; TANTALUM; TANTALUM ALLOYS; TENSILE PROPERTIES; THORIUM; TITANIUM; TITANIUM CARBIDES; TUNGSTEN; U3O8; URANIUM; URANIUM ALLOYS; URANIUM CARBIDES

Citation Formats

Dayton, R. W., and Tipton, Jr., C. R. PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING SEPTEMBER, 1960. Country unknown/Code not available: N. p., 1960. Web. doi:10.2172/4086627.
Dayton, R. W., & Tipton, Jr., C. R. PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING SEPTEMBER, 1960. Country unknown/Code not available. doi:10.2172/4086627.
Dayton, R. W., and Tipton, Jr., C. R. Sat . "PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING SEPTEMBER, 1960". Country unknown/Code not available. doi:10.2172/4086627. https://www.osti.gov/servlets/purl/4086627.
@article{osti_4086627,
title = {PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING SEPTEMBER, 1960},
author = {Dayton, R. W. and Tipton, Jr., C. R.},
abstractNote = {The study of possible reactions induced by the application of high pressures at high temperatures was concentrated on U/sub 3/O/sub 8/-Al/sub 2/O/ sub 3/. Data are reported on the effects of temperature on the tensile properties of fully recryatallized Cr-- Hb, Nb-- V, Nb-- Zr, and Cr-- Nb-- Zr alloys. The effect of radiation on the creep properties of Zircaloy-2 at elevated temperatures is being studied. Magnesium oxides are being evaluated as a fuel matrix material for uranium dioxide. Specimens of niobium-base birary alloys containing 10, 20, and 30 wt.% uranium and ternary alloys containing 20 wt.% uranium with 10 or 20 wt.% Zr were prepared with enriched uranium for irradiation tests. Pu--Nb, Pu-- Th, Mo-- Pu-- U, and Nb-- Pu--U alloys were selected as candidates in the search for improved irradiation resistance. Specimens consisting of uranium nitride dispersed in C, Cr, Fe, Mo, Nb, Ta, Ti, W, and Zr were fabricated and heat-treated to evaluate compatibility. A summary of results is presented from 3 hr, 1430 deg C, 5 tsi hydrostatic pressings of various types of uranium carbide and U--C -Nb systems. The effects of heat- treatment on some properties of U-C syatems are presented. Data are presented on the corrosion resistance of UC -Mo/sub 2/C, UC --NbC, UC -TiC, UC --VC, Uc -- ZrC --Mo/sub 2/C, and UC -- ZrC --VC to Santowax R at 350 C for7 days. The development of powder metallurgy and melting and casting techniques for uranium nitrides is reported. Creep and atress-rupture tests are reported on Zircaloy-2 sheet specimens. Fission gas release experiments are reported on fueled-graphite spheres in suppent of the Pebble-bed Reactor. In the development of container materials for LAMPRE applications, the fabrication behavior of 13 birary tantalum- base alloys was investigated. Radiation-effects studies of fuel specimens of UO/ sub 2/ dispersed in BeO and Al/sub 2/O/sub 3/ and UC and UC/sub 2/ dispersed in graphite are reported. Studies are being conducted to develop an instrumented fuel plate for irradiation in the SM-1 and to develop fuel, absorber, and suppressor materials for the SM-2. A process is being investigated for the fabrication of dense BeO--UC/sub 2/ fuel pellets by cold pressing and sintering. A program to study the effects of irradiation on Hastelloy-X-clad compacts of highly enriched UC/sub 2/ is in progress. Thorium samples were nickel plated for corrosion testing under atmospheric conditions and in watersaturated air at 120 and 200 deg F. Data are reported on the corrosion of thorium, uranium, and U--10 wt.% Mo alloy under three types of conditions. (For preceding period see BMI- 1464.) (W.L.H.)},
doi = {10.2172/4086627},
journal = {},
number = ,
volume = ,
place = {Country unknown/Code not available},
year = {1960},
month = {10}
}